Current Status of the Post Boiling Transition Research in Japan Integrity Evaluation of Nuclear Fuel Assemblies after Boiling Transition and Development of Rewettin Correlations
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概要
- 論文の詳細を見る
Development of rewetting correlation formula was the key to predict fuel-cladding temperature after Boiling Transition (BT). Japanese BWR utilities and vendors performed some tests of rewetting and made two rewetting correlation formulas. The effect on fuel integrity after BT depends on temperature of fuel rod and time of dryout. Main cause of losing fuel integrity during BWR’s Anticipated Operational Occurrences (AOO) after BT is embrittlement of the claddings due to oxidation. Ballooning of fuel rod is excepted because its pressure boundary isn’t broken. In Japan, the Standards Committee of Atomic Energy Society of Japan (AESJ) is making post BT standard. This standard provides guidelines based on the latest knowledge to judge fuel integrity in case of BT and the validity of reusing the fuel assembly that experienced BT in BWRs.
- 一般社団法人 日本原子力学会の論文
- 2003-10-25
著者
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Kudo Yoshiro
Global Nuclear Fuel
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Kudo Yoshiro
Global Nuclear Fuel Japan Co. Ltd.
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MOROOKA Shinichi
Toshiba Corporation
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HARA Takashi
Tokyo Electric Power Company
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MIZOKAMI Shinya
Tokyo Electric Power Company
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KOMURA Seiichi
Global Nuclear Fuel Japan, Co. Ltd.,
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NAGATA Yoshifumi
Hitachi, Ltd
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Nagata Yoshifumi
Hitachi Ltd
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Komura Seiichi
Global Nuclear Fuel Japan Co. Ltd.
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Morooka Shinichi
Toshiba
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MIZOKAMI Shinya
Tokyo Electric Power Co., Inc (TEPCO)
関連論文
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- Boiling Heat Transfer Characteristics with Highly Wettable Heated Surface under Forced Convection Conditions(International Conferences on Power and Energy System)
- D108 Boiling heat transfer characteristics with highly wettable heated surface under forced convection conditions
- Two-phase Flow Patterns in a Four by Four Rod Bundle
- Effect of Radiation Induced Surface Activation on Quenching Condition
- Current Status of the Post Boiling Transition Research in Japan Integrity Evaluation of Nuclear Fuel Assemblies after Boiling Transition and Development of Rewettin Correlations
- Analytical Study on Detailed Void Distributions Inside BWR Fuel Bundle under Turbine Trip Event Considering Time-Dependent Pin Power Distributions
- Stability Estimation of ABWR on the Basis of Noise Analysis